AR102985A1 - HORIZONTAL STEAM GENERATOR FOR THE REACTOR ASSEMBLY WITH PRESSURE WATER REACTOR AND THE REACTOR ASSEMBLY WITH THE INDICATED STEAM GENERATOR - Google Patents

HORIZONTAL STEAM GENERATOR FOR THE REACTOR ASSEMBLY WITH PRESSURE WATER REACTOR AND THE REACTOR ASSEMBLY WITH THE INDICATED STEAM GENERATOR

Info

Publication number
AR102985A1
AR102985A1 ARP150104053A ARP150104053A AR102985A1 AR 102985 A1 AR102985 A1 AR 102985A1 AR P150104053 A ARP150104053 A AR P150104053A AR P150104053 A ARP150104053 A AR P150104053A AR 102985 A1 AR102985 A1 AR 102985A1
Authority
AR
Argentina
Prior art keywords
steam generator
heat exchange
horizontal
exchange tubes
reactor
Prior art date
Application number
ARP150104053A
Other languages
Spanish (es)
Inventor
Vladimirovich Safronov Aleksey
Aleksandrovich Lakhov Dmitriy
Original Assignee
Jsc Experimental And Design Organization «Gidropress» («Okb Gidropress»)
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by Jsc Experimental And Design Organization «Gidropress» («Okb Gidropress») filed Critical Jsc Experimental And Design Organization «Gidropress» («Okb Gidropress»)
Publication of AR102985A1 publication Critical patent/AR102985A1/en

Links

Classifications

    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F22—STEAM GENERATION
    • F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
    • F22B1/00—Methods of steam generation characterised by form of heating method
    • F22B1/02—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F22—STEAM GENERATION
    • F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
    • F22B1/00—Methods of steam generation characterised by form of heating method
    • F22B1/02—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers
    • F22B1/023—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers with heating tubes, for nuclear reactors as far as they are not classified, according to a specified heating fluid, in another group
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F22—STEAM GENERATION
    • F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
    • F22B1/00—Methods of steam generation characterised by form of heating method
    • F22B1/02—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers
    • F22B1/16—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers the heat carrier being hot liquid or hot vapour, e.g. waste liquid, waste vapour
    • F22B1/162—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers the heat carrier being hot liquid or hot vapour, e.g. waste liquid, waste vapour in combination with a nuclear installation
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F22—STEAM GENERATION
    • F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
    • F22B29/00—Steam boilers of forced-flow type
    • F22B29/06—Steam boilers of forced-flow type of once-through type, i.e. built-up from tubes receiving water at one end and delivering superheated steam at the other end of the tubes
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F22—STEAM GENERATION
    • F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
    • F22B37/00—Component parts or details of steam boilers
    • F22B37/002—Component parts or details of steam boilers specially adapted for nuclear steam generators, e.g. maintenance, repairing or inspecting equipment not otherwise provided for
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F22—STEAM GENERATION
    • F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
    • F22B37/00—Component parts or details of steam boilers
    • F22B37/02—Component parts or details of steam boilers applicable to more than one kind or type of steam boiler
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F22—STEAM GENERATION
    • F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
    • F22B37/00—Component parts or details of steam boilers
    • F22B37/02—Component parts or details of steam boilers applicable to more than one kind or type of steam boiler
    • F22B37/22—Drums; Headers; Accessories therefor
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F22—STEAM GENERATION
    • F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
    • F22B37/00—Component parts or details of steam boilers
    • F22B37/02—Component parts or details of steam boilers applicable to more than one kind or type of steam boiler
    • F22B37/22—Drums; Headers; Accessories therefor
    • F22B37/228—Headers for distributing feedwater into steam generator vessels; Accessories therefor
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F28—HEAT EXCHANGE IN GENERAL
    • F28D—HEAT-EXCHANGE APPARATUS, NOT PROVIDED FOR IN ANOTHER SUBCLASS, IN WHICH THE HEAT-EXCHANGE MEDIA DO NOT COME INTO DIRECT CONTACT
    • F28D7/00—Heat-exchange apparatus having stationary tubular conduit assemblies for both heat-exchange media, the media being in contact with different sides of a conduit wall
    • F28D7/16—Heat-exchange apparatus having stationary tubular conduit assemblies for both heat-exchange media, the media being in contact with different sides of a conduit wall the conduits being arranged in parallel spaced relation
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F28—HEAT EXCHANGE IN GENERAL
    • F28F—DETAILS OF HEAT-EXCHANGE AND HEAT-TRANSFER APPARATUS, OF GENERAL APPLICATION
    • F28F9/00—Casings; Header boxes; Auxiliary supports for elements; Auxiliary members within casings
    • F28F9/007—Auxiliary supports for elements
    • F28F9/013—Auxiliary supports for elements for tubes or tube-assemblies
    • F28F9/0132—Auxiliary supports for elements for tubes or tube-assemblies formed by slats, tie-rods, articulated or expandable rods
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F28—HEAT EXCHANGE IN GENERAL
    • F28D—HEAT-EXCHANGE APPARATUS, NOT PROVIDED FOR IN ANOTHER SUBCLASS, IN WHICH THE HEAT-EXCHANGE MEDIA DO NOT COME INTO DIRECT CONTACT
    • F28D21/00—Heat-exchange apparatus not covered by any of the groups F28D1/00 - F28D20/00
    • F28D2021/0019—Other heat exchangers for particular applications; Heat exchange systems not otherwise provided for
    • F28D2021/0061—Other heat exchangers for particular applications; Heat exchange systems not otherwise provided for for phase-change applications
    • F28D2021/0064—Vaporizers, e.g. evaporators
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

Landscapes

  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • General Engineering & Computer Science (AREA)
  • Thermal Sciences (AREA)
  • Mechanical Engineering (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • Sustainable Development (AREA)
  • Sustainable Energy (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Medicines That Contain Protein Lipid Enzymes And Other Medicines (AREA)
  • Structures Of Non-Positive Displacement Pumps (AREA)

Abstract

La presente pertenece a la industria de la energía eléctrica, en particular, a los generadores de vapor horizontales para plantas nucleares con reactor ergogeno de agua a presión (VVER) y al conjunto del reactor con el VVER y el generador de vapor horizontal. El conjunto del reactor con el VVER con generador de vapor horizontal comprende un reactor nuclear con cuatro bucles de circulación, cada uno de los cuales incluye un generador de vapor con un haz horizontal de tubos de intercambio de calor, divididos en paquetes con pasillos intertubulares y conectados a los colectores del caloportador del circuito primario en el interior de la carcasa cilíndrica con fondos elípticos; la bomba principal de circulación, así como la tubería principal de circulación del caloportador del circuito primario. El diámetro interior de la carcasa Dᶜₐʳᶜₐₛₐ, la distancia S entre los ejes de los colectores del caloportador del circuito primario en dirección transversal y la longitud del generador de vapor Lᶜ en las superficies interiores de los fondos elípticos se seleccionan, respectivamente, según las relaciones: donde: D es la producción nominal de vapor del generador de vapor, t/h; Nₜᵘᵇ es el número de tubos de intercambio de calor en la carcasa del generador de vapor, pza.; Sᵛ y Sₕ, es el paso entre los tubos de intercambio de calor respectivamente en la hilera horizontal y vertical del haz de intercambio de calor, mm.; k es el índice de composición del haz de intercambio de calor en paquetes; H es la altura del relleno de la carcasa del generador de vapor, mm.; Dᶜₒₗ es el diámetro exterior del colector del circuito primario en la parte de perforación, mm.; a es el ángulo central de la flexión de tubos de intercambio de calor, grados; B₁ y B₂ es el ancho del pasillo central del haz de tubos de intercambio de calor y el ancho del pasillo del haz de tubos de intercambio de calor, ubicado enfrente del colector del caloportador, respectivamente, mm.; Sᶜₒₗ es el paso circular de los tubos de intercambio de calor en la superficie exterior del colector del caloportador, mm.; Hₛⁱᶜ es el área de la superficie de intercambio de calor del generador de vapor, m²; d es el diámetro exterior de los tubos de intercambio de calor, mm.; D es la distancia desde el tubo exterior del haz de intercambio de calor hasta la superficie interior del fondo del generador de vapor a lo largo del eje longitudinal del generador de vapor, mm.; al mismo tiempo el ángulo a de flexión de los tubos de intercambio de calor y la distancia D se han seleccionado según los siguientes rangos: 90º £ a £ 150º y 300 mm. £ D £ 1.000 mm.This belongs to the electric power industry, in particular, to horizontal steam generators for nuclear plants with an ergogenous pressurized water reactor (VVER) and to the reactor assembly with the VVER and the horizontal steam generator. The reactor assembly with the VVER with horizontal steam generator comprises a nuclear reactor with four circulation loops, each of which includes a steam generator with a horizontal beam of heat exchange tubes, divided into packages with inter-tubular aisles and connected to the primary circuit heat collector collectors inside the cylindrical housing with elliptical bottoms; the main circulation pump, as well as the main circulation pipe of the primary circuit heat carrier. The inner diameter of the housing Dᶜₐʳᶜₐₛₐ, the distance S between the axes of the primary heat exchanger collectors in the transverse direction and the length of the steam generator Lᶜ on the inner surfaces of the elliptical bottoms are selected, respectively, according to the ratios: where: D is the nominal steam production of the steam generator, t / h; Nₜᵘᵇ is the number of heat exchange tubes in the steam generator housing, pc .; Sᵛ and Sₕ, is the passage between the heat exchange tubes respectively in the horizontal and vertical row of the heat exchange beam, mm .; k is the composition index of the heat exchange bundle beam; H is the height of the steam generator housing filling, mm .; Dᶜₒₗ is the outer diameter of the primary circuit collector in the drilling part, mm .; a is the central angle of the flexion of heat exchange tubes, degrees; B₁ and B₂ is the width of the central aisle of the heat exchange tube bundle and the width of the aisle of the heat exchange tubing bundle, located in front of the heat carrier manifold, respectively, mm .; Sᶜₒₗ is the circular passage of the heat exchange tubes on the outer surface of the heat carrier manifold, mm .; Hₛⁱᶜ is the area of the heat exchange surface of the steam generator, m²; d is the outer diameter of the heat exchange tubes, mm .; D is the distance from the outer tube of the heat exchange beam to the inner surface of the bottom of the steam generator along the longitudinal axis of the steam generator, mm .; at the same time the angle a of flexion of the heat exchange tubes and the distance D have been selected according to the following ranges: £ 90 to £ 150 and 300 mm. £ D £ 1,000 mm.

ARP150104053A 2014-12-12 2015-12-11 HORIZONTAL STEAM GENERATOR FOR THE REACTOR ASSEMBLY WITH PRESSURE WATER REACTOR AND THE REACTOR ASSEMBLY WITH THE INDICATED STEAM GENERATOR AR102985A1 (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
RU2014150427/06A RU2583324C1 (en) 2014-12-12 2014-12-12 Horizontal steam generator for reactor plant with water-cooled power reactor and reactor plant with said steam generator

Publications (1)

Publication Number Publication Date
AR102985A1 true AR102985A1 (en) 2017-04-05

Family

ID=55959896

Family Applications (1)

Application Number Title Priority Date Filing Date
ARP150104053A AR102985A1 (en) 2014-12-12 2015-12-11 HORIZONTAL STEAM GENERATOR FOR THE REACTOR ASSEMBLY WITH PRESSURE WATER REACTOR AND THE REACTOR ASSEMBLY WITH THE INDICATED STEAM GENERATOR

Country Status (14)

Country Link
US (1) US20170321879A1 (en)
EP (1) EP3236150A4 (en)
JP (1) JP2018506724A (en)
KR (1) KR20170103810A (en)
CN (1) CN107250664B (en)
AR (1) AR102985A1 (en)
BR (1) BR112017012525A2 (en)
CA (1) CA2970600A1 (en)
EA (1) EA032753B1 (en)
JO (1) JOP20150305B1 (en)
RU (1) RU2583324C1 (en)
UA (1) UA121984C2 (en)
WO (1) WO2016093736A2 (en)
ZA (1) ZA201704656B (en)

Families Citing this family (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
RU2583324C1 (en) * 2014-12-12 2016-05-10 Открытое акционерное общество "Ордена Трудового Красного Знамени и ордена труда ЧССР опытное конструкторское бюро "ГИДРОПРЕСС" (ОАО ОКБ "ГИДРОПРЕСС") Horizontal steam generator for reactor plant with water-cooled power reactor and reactor plant with said steam generator
RU2583321C1 (en) * 2014-12-12 2016-05-10 Открытое акционерное общество "Ордена Трудового Красного Знамени и ордена труда ЧССР опытное конструкторское бюро "ГИДРОПРЕСС" (ОАО ОКБ "ГИДРОПРЕСС") Steam generator with horizontal beam of heat exchange pipes and assembly method thereof
CN106340328B (en) * 2016-09-09 2022-05-20 中国核工业二三建设有限公司 Alignment and leveling method for nuclear power station pressure vessel cylinder and steam generator
CN107688718B (en) * 2017-09-15 2022-11-18 中国核电工程有限公司 Design method for avoiding using damper to resist dynamic load of high-temperature pipeline
CN109990256B (en) * 2019-04-09 2020-12-04 中国核动力研究设计院 Main steam pipeline arrangement structure and method for modular small reactor
CN112829346A (en) * 2020-12-31 2021-05-25 江苏核电有限公司 Device and method for repairing insulation of heating pipe of electric heater of voltage stabilizer of nuclear power station
CN112923347A (en) * 2021-01-20 2021-06-08 西安石油大学 Novel annular array flow distribution device

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RU2583324C1 (en) * 2014-12-12 2016-05-10 Открытое акционерное общество "Ордена Трудового Красного Знамени и ордена труда ЧССР опытное конструкторское бюро "ГИДРОПРЕСС" (ОАО ОКБ "ГИДРОПРЕСС") Horizontal steam generator for reactor plant with water-cooled power reactor and reactor plant with said steam generator
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Also Published As

Publication number Publication date
CN107250664A (en) 2017-10-13
RU2583324C1 (en) 2016-05-10
JOP20150305B1 (en) 2023-09-17
US20170321879A1 (en) 2017-11-09
JP2018506724A (en) 2018-03-08
WO2016093736A9 (en) 2016-08-25
EP3236150A2 (en) 2017-10-25
BR112017012525A2 (en) 2018-02-27
CN107250664B (en) 2019-10-11
EA201650102A1 (en) 2017-09-29
KR20170103810A (en) 2017-09-13
WO2016093736A2 (en) 2016-06-16
EP3236150A4 (en) 2018-10-31
CA2970600A1 (en) 2016-06-16
ZA201704656B (en) 2019-11-27
UA121984C2 (en) 2020-08-25
EA032753B1 (en) 2019-07-31
WO2016093736A3 (en) 2016-08-04

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